| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 4.692 (b) | 5.278 (b) | 1.125 | − | 4.639 (b) | 5.522 (b) |
| 2 | (n,elastic) | 4.566 (b) | 5.153 (b) | 1.128 | − | 2.914 (b) | 4.767 (b) |
| 4 | (n,inelastic) | ( E-thr = 1.311 MeV ) | 456.8 (mb) | 663.3 (mb) | |||
| 16 | (n,2n) | ( E-thr = 10.40 MeV ) | 1.223 (b) | 370.9 (μb) | |||
| 17 | (n,3n) | ( E-thr = 18.21 MeV ) | − | 50.55 (nb) | |||
| 22 | (n,na) | ( E-thr = 2.656 MeV ) | 1.993 (mb) | 476.4 (nb) | |||
| 28 | (n,np) | ( E-thr = 8.557 MeV ) | 526.9 (μb) | 310.3 (nb) | |||
| 102 | (n,γ) | 125.3 (mb) | 125.3 (mb) | 1.000 | 6.665 (b) | 1.025 (mb) | 89.85 (mb) |
| 103 | (n,p) | ( E-thr = 1.212 MeV ) | 35.71 (mb) | 44.57 (μb) | |||
| 104 | (n,d) | ( E-thr = 6.226 MeV ) | 330.3 (μb) | 113.8 (nb) | |||
| 105 | (n,t) | ( E-thr = 9.518 MeV ) | 1.753 (nb) | 4.114 (nb) | |||
| 106 | (n,He-3) | ( E-thr = 6.898 MeV ) | 143.4e-15 (b) | 3.950e-12 (b) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 302.2 (μb) | 6.619 (mb) | 18.10 (μb) |
|
These cross sections are calculated from JENDL-3.2 at 300K.
The background color of each cell noted a cross section means the order of the cross-section value.
The unit of cross section, (b), means barns, and SI prefixes are used as following.
(kb) → 103(b), (mb) → 10−3(b),
(μb) → 10−6(b), (nb) → 10−9(b).
MT is a number that defines a reaction type. For the relation between MT and reaction type, please see here or refer to the manual of ENDF formats.
Maxwellian Average :
where T denotes the temperature, and kB the Boltzmann constant.
The upper and lower limits of integration, EL and EU
are set to 10−5 eV and 10 eV, respectively.
Resonance Integral :
with EL = 0.5 eV and EU = 10 MeV.
U-235 Thermal Fission-Neutron Spectrum Average (Fiss. Spec. Average) :
with EL = 10−5 eV and EU = 20 MeV.
The parameters a and b are 0.988 MeV and 2.249 MeV−1, respectively.
Westcott g-factor :
|